TENDL-2015 Nuclear data library
Neutron sub-library for Ac (Z=89) and A=214: partial cross sections to discrete levels
Reaction types
Reaction #
214
Ac(n,a)
214
Ac(n,d)
214
Ac(n,g)
214
Ac(n,h)
214
Ac(n,inl)
214
Ac(n,p)
214
Ac(n,t)
214
Ac(n,a)